Published October 2000
| Version v1
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Pin-by-pin modeling of fuel cycle and reactivity initiated accidents in LWR
Creators
- 1. RRC 'Kurchatov Institute', Nuclear Safety Institute, Moscow (Russian Federation)
Description
This study deals with validation results for pin-by-pin methods to model fuel cycle and reactivity initiated accidents (RIAs) in LWR. Both methods are based on a heterogeneous pin-by-pin reactor model, realized in the BARS code. Validation results are presented for separate steps of WWER fuel cycle modeling. Features and advantages of a pin-by-pin approach for modeling of LWR RIA shown on the basis of calculations of control rod ejection accidents (REAs) in South Ukrainian NPP Unit 1 WWER-1000 and Three Mile Island Unit 1 (TMI-1) PWR at the end of cycles. Calculations were performed using the coupled RELAP-BARS code. Effects of pin-by-pin power and burnup distribution on estimation of the accident consequences are considered. (Authors)
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32068947.pdf
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-622-0
- Imprint Title
- Proceedings of the Tenth Symposium of Atomic Energy Research. V. I
- Imprint Pagination
- 500 p.
- Journal Page Range
- p. 365-385
- Report number
- INIS-SK--01-008
Conference
- Title
- 10. Symposium of Atomic Energy Research on WWER Physics and Reactor Safety
- Dates
- 18-22 Sep 2000
- Place
- Moscow (Russian Federation)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 32068947
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENCHMARKS; BURNUP; CALCULATION METHODS; COMPUTER CODES; EXPERIMENTAL DATA; FUEL CYCLE; HETEROGENEOUS REACTOR CORES; POWER DISTRIBUTION SYSTEMS; REACTOR ACCIDENTS; ROD EJECTION ACCIDENTS; SAFETY ANALYSIS; SOUTH UKRAINIAN-1 REACTOR; STANDARDIZATION; VALIDATION; WWER TYPE REACTORS; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR CORES; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 17 refs., 9 figs., 8 tabs. Imprint:Next corporations organizations: Dukovany NPP, CEZ, a.s., 675 50 Dukovany (CZ); Energoprojekt Praha a.s., 140 21 Praha 4 (Czech Republic); VTT Energy, Technical Research Centre of Finland, P.O.Box 1604, FIN-02044 VTT (Finland); RRC 'Kurchatov Institute, 123182 Moscow (Russian Federation); INRE-Bulgarian Academy of Science, Varna (Bulgaria); Studsvik Scandpower AS, Box 15, N-2027 Kjeller (Norway); All-Russia Scientific and Research Institute for the Operation of Nuclear Power Plants, Ferganskaya ul. 25, 109507 Moscow (RU); Institute of Atomic Energy, 05-400 Otwock-Swierk (PL); Fortum Engineering Ltd., Rajatorpantie 8, Vantaa, POB 10-FIN-00048 FORTUM (FI); Power and Engineering Plant Company, K.A.B GmbH, Moellendorfstr. 52, D-10367 Berlin (DE);NPP Kozloduy, NPP 3321, Kozloduy (BG); DSR GmbH, Beilsteiner Str. 120, D-12681 Berlin (DE); Institute of Nuclear Techniques oh the TUB, H-1521 (HU); IPPE, 249020 Bandarenko sq. 1, Obninsk, Kaluga Region (RU); VKTA, Postfach 510119 D-01314 Dresden (DE); Slovenske elektrarne, a.s., Hranicna 12, 827 36 Bratislava 21 (SK)